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Category:E-Mail
MONTHYEARML24024A0182024-01-24024 January 2024 LTR-23-0216-1 - (E-Mail) Turkey Point Nuclear Plant, Units 3 and 4 - 10 CFR 2.206 Petition -Turkey Point and PWR RPV Embrittlement E-Mail Closure Letter to Petitioner, January 23, 2024 ML24023A0622024-01-10010 January 2024 10 CFR 2.206 Petition - LTR-23-0216-1 - Turkey Point and PWR RPV Embrittlement - E-mail Final Determination Status to Petitioner - 1-10-2024 - L-2023-CRS-0005 IR 05000250/20240102024-01-0505 January 2024 Focused Engineering Inspection 05000250/2024010 and 05000251/2024010 ML23347A0772023-12-13013 December 2023 NRR E-mail Capture - Acceptance Review - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - LAR to Transition to 24-Month Fuel Cycles (L-2023-LLA-00161) ML23341A0602023-12-0707 December 2023 NRR E-mail Capture - Acceptance Review - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Exemption Request for Use of Axiom Fuel Cladding (L-2023-LLE-0036) ML23317A3752023-11-0808 November 2023 NRR E-mail Capture - Acceptance Review - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - LAR to Update SFP Criticality Analysis (L-2023-LLA-0142) ML23307A2382023-11-0303 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 - Initial Assessment; Turkey Point Subsequent License Renewal with Petitioner 11/3/2023 - L-2023-CRS-0005 ML23333A0092023-10-27027 October 2023 Attachment a - NRC Extension of Comment Period-1 ML23265A2692023-09-15015 September 2023 Turkey Point,_Rp Document Request 2023-004 ML23226A0752023-08-14014 August 2023 NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - RCP LAR (L-2022-LLA-0128) ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23171B0532023-06-20020 June 2023 NRR E-mail Capture - Change in Estimated Review Schedule for Turkey Point Improved Standard Technical Specifications (ITS) LAR (L-2022-LLI-0002) ML23198A0592023-05-22022 May 2023 FPL to Fws, Notification of Doa Crocodile in CCS on 5/22/23 ML23138A0212023-05-17017 May 2023 Telephone Record, Call with Florida Power and Light Regarding Decommissioning Funding Plan Update Dated March 30, 2021 ML23129A8322023-05-0505 May 2023 NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - RCP LAR (L-2022-LLA-0128) ML23109A1862023-04-19019 April 2023 and Turkey Point Acceptance of Requested Licensing Action Proposed Alternative to Asme Section XI Authorizing Implementation of Asme Code Case N-752-1 ML23117A2712023-04-11011 April 2023 NRR E-mail Capture - (External_Sender) Updated Data for Doa Turkey Point American Crocodile at 4/10/2023 ML23067A2812023-03-0808 March 2023 NRR E-mail Capture - (External_Sender) Non-causal American Croc Doa Turkey Point ML23038A1892023-02-0303 February 2023 RP RFI April 2023 ML23006A0262023-01-0505 January 2023 NRR E-mail Capture - Audit Plan - Turkey Point Fire Protection Changes to Support RCP Seal Replacement LAR ML22311A4752022-11-0707 November 2022 NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - ITS ML22293B6562022-10-18018 October 2022 Request for 45 Day Extension of Comment Period of Turkey Point Subsequent License Renewal Scoping Process, Docket Id NRC-2022-0172 by Natural Resources Defense Council, Miami Waterkeeper and Counsel for Friends of the Earth ML22265A1522022-09-21021 September 2022 NRR E-mail Capture - Acceptance Review - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - LAR to Revise Fire Protection Program (L-2022-LLA-0128) ML22258A1862022-09-15015 September 2022 NRR E-mail Capture - Turkey Point Unit Nos. 3 and 4 - Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Requests to Replace Instrumentation with Digital Systems ML22181A0562022-06-30030 June 2022 NRR E-mail Capture - Request for Additional Information - Turkey Point U3 Sgtir (L-2022-LRO-0070) ML22178A1032022-06-25025 June 2022 NRR E-mail Capture - (External_Sender) Turkey Point Doa American Crocodile 6/25/22 ML22147A0672022-05-19019 May 2022 NRR E-mail Capture - (External_Sender) Turkey Point Doa Crocodile 05/19/2022 ML22095A0162022-04-0505 April 2022 NRR E-mail Capture - Verbal Authorization of Turkey Point Nuclear Plant Unit 3 - Icw Relief Request No. 10-II ML22081A0292022-03-21021 March 2022 NRR E-mail Capture - Turkey Point Nuclear Generating Unit No. 3 - Request for Additional Information - Icw Alternative ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21302A0052021-12-23023 December 2021 Email to Nextera/Fpl Re Discussion of Availability of Human Factor Validation Information to Support the Planned Turkey Point Digital I&C License Amendment Request ML21307A2882021-11-18018 November 2021 NRC to Fws, Request to Reinitiate Endangered Species Act Section 7 Consultation for Continued Operation of Turkey Point ML21298A0572021-10-25025 October 2021 NRR E-mail Capture - Final: Tpn Request for Additional Information - Round 2 Concerning Relief Request 10 - Extension EPID: L-2021-LLR-0077 ML21291A1272021-10-14014 October 2021 NRR E-mail Capture - Request for Additional Information - Fifth Ten-Year Inservice Inspection Interval Relief Request No.10 - Extension (L-2021-LLR-0077) ML21270A1652021-09-27027 September 2021 NRR E-mail Capture - Turkey Point Request for Additional Information Concerning Full Spectrum LOCA Methodology - EPID L-2021-LLA-0070 ML21266A2602021-09-22022 September 2021 NRR E-mail Capture - (External_Sender) Partial Sea Turtle Carcass at Turkey Point ML21252A2142021-09-0101 September 2021 NRR E-mail Capture - Final: Turkey Point Units 3 and 4 - Request for Additional Information Concerning Relief Requests 8 and 9 ML21207A1212021-06-30030 June 2021 Fws to NRC, Biological Opinion Notifications to Fws Law Enforcement ML21158A2332021-06-0707 June 2021 NRR E-mail Capture - Acceptance Review: Turkey Point Units 3 and 4 Fifth Ten-Year ISI Extension of ISI RPV Welds from 10 to 20 Years (L-2021-LLR-0038) ML21154A0872021-06-0202 June 2021 NRR E-mail Capture - 06/02/2021 Print a Logbook Entry: Turkey Point Endangered Species Report Regarding Injured American Crocodiles ML21154A0862021-05-25025 May 2021 NRR E-mail Capture - Acceptance Review: Turkey Point - Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology ML21140A0672021-05-13013 May 2021 NRR E-mail Capture - (External_Sender) Regarding Doa American Crocodile Report 5-13-21 ML21131A1362021-05-0404 May 2021 NRR E-mail Capture - (External_Sender) 5/4/2021 Report Regarding Doa American Crocodile ML21097A1832021-03-30030 March 2021 NRR E-mail Capture - Endangered Species Death Report from Turkey Point Regarding Incident on 03/30/2021 ML21084A1312021-03-18018 March 2021 NRR E-mail Capture - (External_Sender) Deceased American Crocodile Found Outside FPL Property Line ML21056A0002021-02-24024 February 2021 NRR E-mail Capture - Endangered Species - 2/24/2021 Logbook Entry Regarding an American Crocodile ML21029A0172021-01-25025 January 2021 NRR E-mail Capture - 1/25/2021 Logbook Entry Regarding an American Crocodile Reported in the Owner Controlled Area ML21025A4152021-01-25025 January 2021 NRR E-mail Capture - 10 CFR 2.206 Petition Dated January 10, 2021 - Open Phase Condition Implementation ML20346A1022020-12-0808 December 2020 NRR E-mail Capture - Response: September 17, 2020 Submittal to the Nuclear Regulatory Commission ML20218A5502020-08-0505 August 2020 Florida Power & Light Letter L-2020-127: FPL QAPD for 10 CFR 52 Licenses FPL-2 Revision Summary 2024-01-05
[Table view] Category:Report
MONTHYEARML23333A0172023-11-27027 November 2023 Attachment I - Chin - the Cooling Canal System at the FPL-Turkey-Point Power Station ML23333A0142023-11-27027 November 2023 Attachment F - Groundwater Tek Inc - Peer Review Study Final-1 ML24012A0422023-11-16016 November 2023 FAQ 23-03 Turkey Point IE01 Proposed NRC Response ML23265A5512023-09-22022 September 2023 Enclosure 3: WCAP-18830-NP, Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-110, License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary)2022-08-26026 August 2022 License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary) L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-038, Emergency Response Data System (Eros) Changes2022-05-17017 May 2022 Emergency Response Data System (Eros) Changes L-2022-073, Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-05-0303 May 2022 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-022, Updated Conditions of Certification Report2022-02-14014 February 2022 Updated Conditions of Certification Report L-2021-182, Summary of Commitment Revisions, Emergency Diesel Generator Fuel Oil Storage Tank Cleaning Inspection Commitment Revisions2021-09-16016 September 2021 Summary of Commitment Revisions, Emergency Diesel Generator Fuel Oil Storage Tank Cleaning Inspection Commitment Revisions L-2021-069, Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds)2021-06-24024 June 2021 Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds) IR 05000250/20200112020-07-23023 July 2020 NRC Inspection Report 05000250-2020011 and 05000251-2020011 and Investigation Report 2-2019-011; and Apparent Violation Final L-2020-073, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request No. 6 and Supplemental Information for Train B CCW Return Piping2020-04-13013 April 2020 Fifth Ten-Year Inservice Inspection Interval Revised Relief Request No. 6 and Supplemental Information for Train B CCW Return Piping ML20098F3412020-04-0707 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information L-2019-204, Request for Use and Approval of Vapor Infusion Technology 90-Day Trial - Notification2019-11-25025 November 2019 Request for Use and Approval of Vapor Infusion Technology 90-Day Trial - Notification L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds L-2019-054, Baffle-Former Bolts Predictive Evaluations2019-03-13013 March 2019 Baffle-Former Bolts Predictive Evaluations ML19072A1622019-03-0505 March 2019 National Park Service, Southeast Regional Office, Comments Dated March 5, 2019, on Turkey Point Nuclear Generating Units 3 and 4 Preliminary Draft SEIS Regarding Subsequent License Renewal ML18353A8352018-12-31031 December 2018 Biological Assessment for the Turkey Point Units 3 and 4 Proposed Subsequent License Renewal ML18299A1162018-10-15015 October 2018 Structural Integrity Associates Engineering Report No. 1700109.401P, Revision 7 - Redacted, Evaluation of Environmentally-Assisted Fatigue for Turkey Point Units 3 and 4 for Subsequent License Renewal L-2018-174, Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines2018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines ML18299A1182018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.304, Revision 3, Fatigue Crack Growth Evaluation, October 12, 2018 L-2018-187, Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation2018-10-0505 October 2018 Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation L-2018-169, Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review2018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review L-2018-173, Notification of Request for Use and Approval of Polyacrylic Acid Pilot Program2018-09-21021 September 2018 Notification of Request for Use and Approval of Polyacrylic Acid Pilot Program ML18254A3412018-09-11011 September 2018 Fish and Wildlife Service'S List of Migratory Birds Near Turkey Point ML18227B5212018-08-15015 August 2018 Submit Attachment a, Annual Hourly Percent Frequency of Vertical and Horizontal Stability Categories by Wind Direction and Wind Speed ML18227A2902018-08-15015 August 2018 Submit Report Contains Official Summary of Startup Physics Tests, Unit 4 Cycle Iii. the Tests Were Conducted in Accordance with Operating Procedure 0204.5, Startup Sequence After Refueling L-2018-098, Annual Report for the AP1000 Standard Plant Design, 2017 Model Year 10 CFR 50.462018-04-18018 April 2018 Annual Report for the AP1000 Standard Plant Design, 2017 Model Year 10 CFR 50.46 L-2018-054, Attachment B: Process Control Program, 0-HPA-045, Revision 0A, Issued 2/16/172018-02-16016 February 2018 Attachment B: Process Control Program, 0-HPA-045, Revision 0A, Issued 2/16/17 L-2017-148, Special Report - Accident Monitoring Instrumentation2017-08-11011 August 2017 Special Report - Accident Monitoring Instrumentation L-2017-123, Special Report - Standby Steam Generator Feedwater Pumps Inoperable2017-06-29029 June 2017 Special Report - Standby Steam Generator Feedwater Pumps Inoperable L-2017-124, Flooding Focused Evaluation Summary2017-06-29029 June 2017 Flooding Focused Evaluation Summary L-2017-014, Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 20162017-04-17017 April 2017 Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 2016 L-2016-226, NEI 12-06, Revision 2, Appendix G, G.4.2 Mitigating Strategies Assessment Flex Strategies Report for the New Flood Hazard Information2016-12-20020 December 2016 NEI 12-06, Revision 2, Appendix G, G.4.2 Mitigating Strategies Assessment Flex Strategies Report for the New Flood Hazard Information L-2016-058, Licensee Qualification for Performing Dynamic Rod Worth Measurement Analysis2016-03-23023 March 2016 Licensee Qualification for Performing Dynamic Rod Worth Measurement Analysis ML16013A4722016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task L-2015-313, Special Report - Accident Monitoring Instrumentation2015-12-18018 December 2015 Special Report - Accident Monitoring Instrumentation L-2015-137, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2015-04-22022 April 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments ML15054A0372015-02-23023 February 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Fire PRA Facts and Observations for Turkey Point Nuclear Generating Stations, Units 3 and 4 ML14338A5542014-12-0404 December 2014 NRC-2013- TN2986-NRC 2014 St. Lucie ML14338A5552014-12-0404 December 2014 NRC-2013-TN3079-NRC 2014 St. Lucie License Renewal L-2014-233, Submittal of Inservice Inspection Program Owner'S Activity Report (OAR-I)2014-07-22022 July 2014 Submittal of Inservice Inspection Program Owner'S Activity Report (OAR-I) L-2014-085, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident 2023-09-22
[Table view] Category:Miscellaneous
MONTHYEARML24012A0422023-11-16016 November 2023 FAQ 23-03 Turkey Point IE01 Proposed NRC Response L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2022-038, Emergency Response Data System (Eros) Changes2022-05-17017 May 2022 Emergency Response Data System (Eros) Changes L-2021-182, Summary of Commitment Revisions, Emergency Diesel Generator Fuel Oil Storage Tank Cleaning Inspection Commitment Revisions2021-09-16016 September 2021 Summary of Commitment Revisions, Emergency Diesel Generator Fuel Oil Storage Tank Cleaning Inspection Commitment Revisions L-2019-204, Request for Use and Approval of Vapor Infusion Technology 90-Day Trial - Notification2019-11-25025 November 2019 Request for Use and Approval of Vapor Infusion Technology 90-Day Trial - Notification L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2018-173, Notification of Request for Use and Approval of Polyacrylic Acid Pilot Program2018-09-21021 September 2018 Notification of Request for Use and Approval of Polyacrylic Acid Pilot Program L-2017-148, Special Report - Accident Monitoring Instrumentation2017-08-11011 August 2017 Special Report - Accident Monitoring Instrumentation L-2017-123, Special Report - Standby Steam Generator Feedwater Pumps Inoperable2017-06-29029 June 2017 Special Report - Standby Steam Generator Feedwater Pumps Inoperable L-2017-124, Flooding Focused Evaluation Summary2017-06-29029 June 2017 Flooding Focused Evaluation Summary L-2016-226, NEI 12-06, Revision 2, Appendix G, G.4.2 Mitigating Strategies Assessment Flex Strategies Report for the New Flood Hazard Information2016-12-20020 December 2016 NEI 12-06, Revision 2, Appendix G, G.4.2 Mitigating Strategies Assessment Flex Strategies Report for the New Flood Hazard Information L-2016-058, Licensee Qualification for Performing Dynamic Rod Worth Measurement Analysis2016-03-23023 March 2016 Licensee Qualification for Performing Dynamic Rod Worth Measurement Analysis ML16013A4722016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task L-2015-313, Special Report - Accident Monitoring Instrumentation2015-12-18018 December 2015 Special Report - Accident Monitoring Instrumentation L-2015-137, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2015-04-22022 April 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments ML15054A0372015-02-23023 February 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Fire PRA Facts and Observations for Turkey Point Nuclear Generating Stations, Units 3 and 4 ML14338A5552014-12-0404 December 2014 NRC-2013-TN3079-NRC 2014 St. Lucie License Renewal ML14338A5542014-12-0404 December 2014 NRC-2013- TN2986-NRC 2014 St. Lucie L-2014-233, Submittal of Inservice Inspection Program Owner'S Activity Report (OAR-I)2014-07-22022 July 2014 Submittal of Inservice Inspection Program Owner'S Activity Report (OAR-I) L-2013-246, Steam Generator Tube Inspection Report2013-09-19019 September 2013 Steam Generator Tube Inspection Report L-2013-258, 10 CFR 71.95 - Cask 8-120B - 60 Day Report2013-09-16016 September 2013 10 CFR 71.95 - Cask 8-120B - 60 Day Report L-2013-237, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report2013-08-20020 August 2013 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report L-2013-140, Special Report - Accident Monitoring Instrumentation2013-04-19019 April 2013 Special Report - Accident Monitoring Instrumentation ML12234A7512012-08-28028 August 2012 Closeout of Review of the One-Time Inspection of Class 1 Small Bore Piping Program Revised Commitment and Inspection Plan L-2012-090, Special Report - Containment Tendon Corrosion Protection Medium Volume Reduction2012-03-0505 March 2012 Special Report - Containment Tendon Corrosion Protection Medium Volume Reduction L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases2011-11-16016 November 2011 Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases ML1122805012011-09-0909 September 2011 Request to Initiate Informal Section 7 Consultation for the Proposed Turkey Point Plant Units 3 and 4 Extended Power Uprate (ME4907 and ME4908) Encl ML1122802922011-09-0909 September 2011 Request to Initiate Informal Section 7 Consultation for the Proposed Turkey Point Plant Units 3 and 4 Extended Power Uprate L-2011-213, Cycle 26 Startup Report2011-07-28028 July 2011 Cycle 26 Startup Report ML1119305872011-03-0404 March 2011 Initial Exam Retake 2011-301 Final Administrative JPMs L-2010-115, 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 20092010-06-0404 June 2010 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 2009 ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML15142A6502009-06-19019 June 2009 Florida Department of Environmental Protection Conditions of Certification - PA 03-45D on Turkey Point Units 3, 4, and 5 L-2008-160, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-08-11011 August 2008 Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. L-2007-129, Emergency Response Data System (ERDS) Maintenance2007-08-20020 August 2007 Emergency Response Data System (ERDS) Maintenance L-2007-095, CFR 50.59 Summary Report, Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering June 13, 2005 Through December 9, 20062007-06-0808 June 2007 CFR 50.59 Summary Report, Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering June 13, 2005 Through December 9, 2006 L-2006-247, Core Operating Limits Report2006-11-27027 November 2006 Core Operating Limits Report L-2006-241, Significance Determination Regarding a Loss of Power to Operating Residual Heat Removal Pump - Additional Information Regarding Gothic Analysis2006-10-17017 October 2006 Significance Determination Regarding a Loss of Power to Operating Residual Heat Removal Pump - Additional Information Regarding Gothic Analysis L-2006-180, Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire2006-07-31031 July 2006 Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire L-2006-131, Wastewater Permit Number FL0001562, Request for Minor Revision Notification2006-05-22022 May 2006 Wastewater Permit Number FL0001562, Request for Minor Revision Notification ML0614301742006-05-0505 May 2006 Biological Opinion Regarding the American Crocodile at Turkey Point L-2006-088, Core Operating Limits Report2006-03-29029 March 2006 Core Operating Limits Report ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0503803942004-03-0505 March 2004 E-mail from P. Fillion to C. Payne - Turkey Point Report Input ML0503803832004-02-0606 February 2004 E-mail from P. Fillion to C. Payne, K. O'Donohue - Evaluation of Valves - Revision ML0503803752004-02-0404 February 2004 E-mail from P. Fillion to C. Payne, K. O'Donohue - Analysis of Two Valves ML0504703632003-09-0909 September 2003 9/9/03 Turkey Point Condition Report 03-1330-1 L-2003-068, Order (EA-03-009) Relaxation Request, Examination Coverage of Reactor Pressure Vessel Head Penetration Nozzles - Supplemental Data2003-03-14014 March 2003 Order (EA-03-009) Relaxation Request, Examination Coverage of Reactor Pressure Vessel Head Penetration Nozzles - Supplemental Data 2023-08-21
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Text
Cjiarlie Payne - Evaluation of Valves - Revision Page 1 From: Paul Fillion To: Charlie Payne; Kathleen O'Donohue Date: 2/6/04 8:38AM
Subject:
Evaluation of Valves - Revision My analysis of two valves has been revised again after discussion with Charley Payne. There would not be any concern with VCT outlet valve spuriously opening because valve is de-energized per procedure.
Also, spurious opening does not necessarily lead to hydrogen entrainment because in most all cases the head pressure of the RWST keeps the VCT outlet check valve closed.
CC: Gerald Wiseman; Necota Staples; Robert Schin I-
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TKAP Avis Pagel II Mail Envelope Properties (402398DE.2A0: 5 51853)
Subject:
Evaluation of Valves - Revision Creation Date: 2/6/04 8:38AM From: Paul Fillion Created By: PJF~nrc.gov Recipients ATLPO.ATLDO DCP (Charlie Payne)
GRW CC (Gerald Wiseman)
KFO (Kathleen ODonohue)
NLS2 CC (Necota Staples)
RPS CC (Robert Schin)
Post Office Route ATLPO.ATLDO Files Size Date & Time TPTFP.wpd 12336 02/06/04 08:20AM MESSAGE 819 02/06/04 08:38AM Options Expiration Date: None Priority: Standard Reply Requested: No Return Notification: None Concealed
Subject:
No Security: Standard
F..;& I I Charlie Pavne - TPTFP.wDd Page 1 I hr Paye
-I - P TURKEY POINT 2004 TFP INSPECTION DISCUSSION OF VCT OUTLET VALVE AND RCP THERMAL BARRIER CCW SUPPLY ISOLATION VALVE by Paul J. Fillion Rev. 1 February 6, 2004 LCV-3-115C There is only one volume control tank outlet valve at Turkey Point, as opposed to the standard two valves in series. The number of this valve is LCV-3-115C for Unit 3. It is a motor operated valve powered from motor control center 3B, which is in Fire Area T63, the control rod drive room. Of course, the valve is open during normal at power operation.
The 11 5C valve has two post-fire shutdown functions. Early on, i.e. from fire initiation to realignment to the RWST or BAT, the function is to remain open to maintain flow through the running charging pump. Later, i.e. to achieve realignment to the RWST or BAT, the function is to close and remain closed. These specific functions relate to the larger shutdown functions of inventory control, reactivity control and RCP seal protection.
The Essential Equipment List states that the valve is important to hot shutdown, cold shutdown and alternative shutdown.
Review of the control circuit and the cable routing leads to the conclusion that a short-circuit between two wires within the same cable or inside a panel in either Fire Area T63 or In the control room, Fire Area MM106, could cause the valve to spuriously close. It is also observed that valve LCV-3-1 158, the RWST to charging pump suction header valve, is designed to open when the VCT outlet valve starts to close. However, no credit is given for this automatic transfer for the control room fire because circuitry for both the 115C and 115B could be subject to the same control room fire. Cable routing will have to be reviewed to determine if automatic transfer could be affected by the MCC room fire. A fire in the Train B 4160 V switchgear room could lead to loss of Train B power, and therefore loss of power to operate the 115C valve.
The licensee's Safe Shutdown Analysis (SSA) recognizes the potential problems with spurious closure of 115C, and resolves the issue by specifying manual actions. FoTrhe control room fire, the SSA specifies immediately stopping charging pump 3B (and also 4B) before leaving the control room and re-establishing charging per ONOP-105. For the fire in the MCC room, the SSA specifies manual action #343, which is really swap over to the RWST source. CR 03-1330, which addresses licensee identified problems with RCP seal protection, summarizes required actions and procedures required to protect the seals for ea6h fire area. I made the point to Bharat Thaker that the CR supercedes the SSA. Bharat said it did not. Since the CR and the SSA don't match, this issue bears further investigation. The CR only recognizes alternative shutdown for the control room fire. For fire in the MCC room, the CR specifies immediately tripping charging pump 3A, de-energizing MCC 3B, and verifying CCW valves 626 and 716B are open [3 min/20min], de-energize charging pump 3B within 15 minutes and start charging pump 3A or 3C within one hour.
ICharlie Pavne - TPTFP~w~d Page 2 I Chrli Ravne - TTPwdPo2 MOV-3-716B This is the RCP thermal barrier CCW supply isolation valve. It is a motor operated valve powered from motor control center 36, the same as 115C. This valve is open in normal at power operation, and its shutdown function is to remain open.
Review of the control circuit and cable routing leads to the conclusion that a short-circuit between two wires within the same cable or inside a panel in Fire Area T63, Fire Area MM106, and Fire Area V67 (based on similarity between Units) could cause the valve to spuriously close. The control circuit also shows that the valve can be operated from the alternate shutdown panel after operation of a transfer switch. It is also observed that a short circuit at Fire Area T63, the MCC room, could cause spurious closure and by pass the torque switch and limit switches.
For the CR fire, the SSA states that electrical isolation is provided. For the MCC room fire, the SSA specifies manual action #217, which is actually a three-part action. First, trip RCPs if valve closes; second, open and disable feeder breaker to MCC; and third, if possible verify locally that W is open (3 minI20 min). For the switchgear room fire [note Unit 3B SWGR room is not on the inspection plan, so I will look at Unit 4 for discussion purposes] the SSA specifies xxxxxx.
CR 1330 specifies the following: Trip charging pump A, use RCP trip criteria in ONOP 41.1, de-energize 716B valve breaker and verify valve open (3 min/20min), and start charging pump A within one hour. The CR also refers to some errors in the analysis with respect to this valve.
Short Term Considerations Control room fire where operators remain in control room Since procedure (which one?)calls for immediately switching away from charging pump 3B to either charging pump 3A or 3C upon recognition of a fire, the charging pump is protected from damage and would be available for use at the alternate shutdown panel if needed later. All RCP seal cooling would be interrupted If the VCT outlet valve closed and CCW valve 716B spuriously closed (two spurious operations). However, spurious operation of beth valves is not considered credible for a smaller control room fire corresponding to a scenario where operators remain in the control room because the controls are on separate panels not near each other.
Spurious closure of the VCT outlet valve could cause damage to either charging pump A or C, but this event is not considered crucial to safe shutdown. Spurious closure of 716B would not by itself interrupt all seal cooling.
Control room fire where decision is made immediately to abandon the control room In this scenario, operators are following ONOP-105, alternate shutdown. The larger control room fire holds the possibility that both the VCT outlet valve and the RCP thermal barrier CCW valve could spuriously close. This procedure, as it existed at the start of the inspection, allowed 15 minutes to get the alternate shutdown facility operational. Then would have performed
ICharlie Payne - TPTFP~wpd Psnpn I I Charlie Payne TPTFP.wod PniI operational steps to reestablish RCP thermal barrier cooling 3 minutes later. The design concept of this procedure in effect had an underlying assumption that two spurious operations terminating all RCP seal cooling would not take place for a period of about 18 minutes immediately following initiation of a fire. The inspection team questioned this concept, pointing out that loss of all RCP seal cooling should be assumed at about T=7 minutes for the large fire scenario and that RCP seal maximum allowable temperature for a running pump could be exceeded well before 18 minutes. The licensee agreed that their procedure was inadequate in this regard and they instituted a standing order to manually de-energize the 716B valve within three minutes of initiating ONOP-1 05. This new procedure was accepted by the team as being timely enough to protect against RCP seal damage, and a seal LOCA, given a reasonable delay time between fire initiation and two spurious operations occurring.
MCC room fire Valves 115C and 716B can spuriously close due to fire induced short circuits. If a reasonable "grace period' for spurious operations is assumed, then procedures specified in CR 03-1330 (i.e. immediately de-energizing MCC 3B and tripping charging pump 3A) would suffice to preclude spurious operations, thus protecting the most important charging pump and maintaining RCP seal cooling. Note that manual opening of valve 716B after a spurious closure may be a problem due to torque switch bypass.
4160 switchaear room B fire The 15C valve should not spuriously close for the switchgear room fire. The 716B valve could spuriously close, and, for a bigger fire, Train B power could be lost. This could cause a temporary loss of seal injection similar to that experienced in a LOOP. It is not apparent from consideration of valves 115C and 716B why CR 1330 specifies the steps mentioned above for the switchgear room fire.
Long Term Considerations Control room fire where operators remain In control room With regard to the VCT outlet valve, a wire burn open means that the valve could not be closed from the control room to execute the swap to RWST or BAT. Alternatively, if the valve can be closed from the control room andbthe-RWST path is establishe-droneshould consider-spurious-opening. The procedures for executing the swap-over to RWST Include a step to de-energize the VCT outlet valve [This step was not specified in the analysis]. If the de-energizing is not done due to operator error, one could consider the consequences. If the VCT outlet valve spuriously opened while the charging pump is taking suction from the RWST, the suction header would be connected to two source tanks with a check valve in the VCT source. This check valve effectively acts as switch turning on the source having the greater head pressure.
So to determine which source would be supplying the flow one would compare the RWST head to the VCT head. The VCT head is determined by height of the water level above the suction header plus the hydrogen blanket pressure. At Turkey Point, since the VCT outlet valve was being de-energized the head pressures were not investigated in detail. Both the charging pumps and the RWST are at ground level, but in all probability the RWST pressure would always dominate.
I[Charlie -Payne - TPTFP.wpd Page 41 14&harflePavne TPTFP.wQd
- Pane 41 Again we would not postulate loss of all seal cooling for this scenario.
Control room fire and alternate shutdown Essentially the same discussion as above, except that valve 716B can be controlled from the alternate shutdown panel.
MCC room fire MCC 3B has already been de-energized immediately after a fire. Therefore spurious operations are not a concern.
4160 V switchpear room B fire The VCT outlet valve should not spuriously operate for the switchgear room fire. Valve 716B has been de-energized.
SUMMARY
OF COMMENTS AND FINDINGS
- 1. Does safe shutdown analysis have to be revised in light of CR 1330?
- 2. Does CR 1330 represent a licensee identified violation?
- 3. ONOP-105 inadequacy identified by Charley Payne.
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